UST920001I4 - Cooper method and apparatus for removing iodine from a nuclear reactor coolant - Google Patents

Cooper method and apparatus for removing iodine from a nuclear reactor coolant Download PDF

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Publication number
UST920001I4
UST920001I4 US920001DH UST920001I4 US T920001 I4 UST920001 I4 US T920001I4 US 920001D H US920001D H US 920001DH US T920001 I4 UST920001 I4 US T920001I4
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United States
Prior art keywords
iodine
reactor coolant
nuclear reactor
removing iodine
cooper
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
    • G21C19/30—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps
    • G21C19/307—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps specially adapted for liquids
    • G21C19/31—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps specially adapted for liquids for molten metals
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Measurement Of Radiation (AREA)
  • Exposure Of Semiconductors, Excluding Electron Or Ion Beam Exposure (AREA)
  • Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

A METHOD AND APPARATUS FOR REMOVING IODINE-131 AND IODINE-125 FROM A LIQUID SODIUM REACTOR COOLANT. NONRADIOCATIVE IODINE IS DISSSOLVED IN HOT LIQUID SODIUM TO INCREASE THE TOTAL IODINE CONCENTRATION. SUBSEQUENT PRECIPITATION OF THE IODINE IN A COLD TRAP REMOVES BOTH THE RADIOACTIVE IODINE ISOTOPES AS WELL AS THE NON-RADIOACTIVE IODINE.

Description

DEFENSIVE PUBLICATION UNITED STATES PATENT OFFICE Published at the request of the applicant or owner in accordance with the Notice of Dec. 18, 1969, 869 0.8. 687. The abstracts of Defensive Publication applications are identified by distinctly numbered series and are arranged chronologically. The heading of each abstract indicates the number of pages of specification, including claims and sheets of drawings contained in the application as originally filed. The files of these applications are available to the public tor inspection and reproduction may be purchased for 30 cents a sheet.
Defensive Publication applications have not been examined as to the merits oi! alleged invention. The Patent Oflice makes no assertion as to the novelty of the disclosed subject matter.
PUBLISHED MARCH 5, 197i T920,001 METHOD AND APPARATUS FOR REMOVING IODINE FROM A NUCLEAR REACTOR COOLANT Martin H. Cooper, Monroeville, Pa., assignor to Westinghouse Elecn'ic Corporation, Pittsburgh, Pa. Filed June 15, 1972, Ser. No. 263,054 Int. Cl. C01b 7/14; G21c 19/30 US. Cl. 176-37 1 Sheet Drawing. 14 Pages Specification A method and apparatus for removing iodine-131 and iodine-125 from a liquid sodium reactor coolant. Nonradioactive iodine is dissolved in hot liquid sodium to increase the total iodine concentration. Subsequent precip itation of the iodine in a cold trap removes both the radioactive iodine isotopes as well as the non-radioactive iodine.
. M. H. COOPER METHOD AND APPARATUS FOR REMOVING IODINE March 5, 1974 FROM A NUCLEAR REACTOR COOLANT Filgd June 15, 1972 lllll mfloo. 023000 Ar 4wwww mm3mmmmm 1064mm 20mm
US920001D 1972-06-15 1972-06-15 Cooper method and apparatus for removing iodine from a nuclear reactor coolant Pending UST920001I4 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US26305472A 1972-06-15 1972-06-15

Publications (1)

Publication Number Publication Date
UST920001I4 true UST920001I4 (en) 1974-03-05

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ID=23000186

Family Applications (1)

Application Number Title Priority Date Filing Date
US920001D Pending UST920001I4 (en) 1972-06-15 1972-06-15 Cooper method and apparatus for removing iodine from a nuclear reactor coolant

Country Status (6)

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US (1) UST920001I4 (en)
JP (1) JPS4950398A (en)
DE (1) DE2329899A1 (en)
FR (1) FR2189820B1 (en)
GB (1) GB1395431A (en)
IT (1) IT993574B (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4088533A (en) 1977-01-18 1978-05-09 The United States Of America As Represented By The United States Department Of Energy Radionuclide trap
US4202730A (en) 1977-01-18 1980-05-13 The United States Of America As Represented By The Department Of Energy Radionuclide deposition control

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CA1071415A (en) * 1975-09-18 1980-02-12 The Government Of The United States As Represented By The United States Department Of Energy Method for the recovery of halogens from sodium
JPS57116296A (en) * 1981-01-13 1982-07-20 Tokyo Shibaura Electric Co Impurity removing device
JPS57117678U (en) * 1981-01-14 1982-07-21
USH262H (en) * 1983-11-25 1987-05-05 The United States Of America As Represented By The United States Department Of Energy Method of and apparatus for removing silicon from a high temperature sodium coolant
DE19638659C1 (en) * 1996-09-20 1998-02-12 Siemens Ag Process and system for reducing the risk of leakage of radioactive iodine when revising primary circuit components of a nuclear power plant

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB985400A (en) * 1960-12-30 1965-03-10 Atomic Energy Authority Uk Improvements in or relating to radioactive materials extraction processes
FR2184516B1 (en) * 1972-05-19 1978-09-01 Labo Electronique Physique

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4088533A (en) 1977-01-18 1978-05-09 The United States Of America As Represented By The United States Department Of Energy Radionuclide trap
US4202730A (en) 1977-01-18 1980-05-13 The United States Of America As Represented By The Department Of Energy Radionuclide deposition control

Also Published As

Publication number Publication date
GB1395431A (en) 1975-05-29
IT993574B (en) 1975-09-30
DE2329899A1 (en) 1974-01-03
JPS4950398A (en) 1974-05-16
FR2189820A1 (en) 1974-01-25
FR2189820B1 (en) 1976-04-30

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